Status of ITER RF systems design

ITER wilt require similar to 100 MW of auxiliary power for plasma heating, current drive and plasma kinetic control functions. As in most of the present-day tokamaks, these functions will be shared among different heating methods. A (negative-ion) neutral beam injection (NBI) and three RF heating and current drive (H&CD) systems-ion cyclotron (ICRF), electron cyclotron (ECRF) and lower hybrid (LBW)-are under conceptual development; the latter being developed by the European Home Team. The three RF H&CD Systems, described in this paper, offer together a range of features and services capable of satisfying all ITER requirements. A standardized design approach is adopted for the systems: all launchers are integrated in ITER equatorial ports, feature an all-metal construction, have a very limited impact on the torus layout, and do not significantly modify vacuum and tritium boundaries. They are removable through the port with similar manual and remote handling operations. A discussion of the RF systems design and of the associated R&D programmes is presented.